ML20217C754
| ML20217C754 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 03/25/1998 |
| From: | Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20217C748 | List: |
| References | |
| NUDOCS 9803270157 | |
| Download: ML20217C754 (7) | |
Text
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NRC FORM 374 u.s. NUCLEAR REGULATORY COMMisslON SIATERIALS LICENSE (q! l-
.S '
93-4381, and Title 10. Code of I g Pursuant to the Atomic Energy Act of 1954, as amended. the Energy Reorganization Act of 1974 (Public Law g federal Regulanons. Chapter I. Parts 30,31,32. 33. 34,35,36. 39,40, and 70, and in reliance on statements and representations her p l by the licensee, a hcense is hereby issued authori/mg the licensee to receis e, acquire. possess, and transfer by product, source. and special nuclear j h material designated below; to use such matenal ror the purposeh) and at the placch) designated below; to dehser or transfer such material to i h ipersons authorved to recene it in accordance with the regulatmns of the apphcable Parth). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954. as amended, and is subject to all applicable rules, regulations, and orders of the j 9
?j Nuclear Regulatory Commission now or hereaf ter in ef fect and to any conditions $lspe 5 5l
$j Licensee 3l Nj $l Sj 1. General Atomics 3. License Number SNM-696, S Amendment 43 $ll t
$ E IXcimbeT3171989 E Sj2. P.O. Box 85608 Sl S
San Diego, Califomia 92186-9784 4. Expiration Date 70-734 f
h g l 5. Docket or w Reference No.
g Ql d 6. liyproduct, Source, and/or 7. Chemical and/or Physical 8. Maximurn Amount that Licensee May Possess at Any One Time 9l h Special Nuclear Material Form Under This License 12l D
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A. Uranium A. Enriched up to 19.99% A. 200 kilograms U-235 $l
.3 U-235 $l 9 Uranium B. Enriched 20 to 100% U-235 B. Less than 5000 gm*
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$l ,
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- yj fj C. U-233 C. Any C. Less than 2000 gm U-233*
{gl !l 5 b"l \
.$ D. Plutonium D. Encapsulated and/or D. Less than 2000 gm 9 sealed sources total Pu' {$Il
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? E. Plutonium E. Bred but unseparated E. Less than 1000 gm $ll
,5 total Pu* $l l
! F. Plutonium F. Plated calibration F. Less than 5 grams
$j' O i 1
% source total Pu* $!i
!j OI fj G. Plutonium G. Sulutions, precipitates G. Less than 5 grams '
$ solids and total Pu* $ll
$ l 3 6l
$ $I
?j The sum total quantity of strategic special nuclear material possessed at any one time must be less $!
than 5,000 grams computed by the formula: I
$jj Grams = grams U-235 in uranium enriched to 20% or more p us 2.5 (grams U-233 + grams $"g i l plutonium) ;l l d
s at
,i J 1
- 9. Authorized place of use: The licensee's San Diego, Califomia site as specified in the aforesaid ,"j!l application and supplemeats. gj I
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NRC'f0RM 374A U.S. NUCLEAR REGULATORY eoMMISSloN PAGE 2 oF 7 PAGES !!
'*' License Number y
- p. SNM-696 Amendment 43 j, pl MATERIALS LICENSE !Auct or Refereme Number j g
SUPPLEMENTARY SHEET 70-734 E
5 E
B E
W E
W E
N E
N B El g 10. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions. El y These sections are part of the license, and the licensee is subject to compliance with all listed E g conditions in each section. E E
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Ni i I I si 8j i I h 7+f X $W fl E Date: bO By: Michael F. Weber B Division of Fuel Cycle Safety H Hj and Safeguards, NMSS El Washington, DC 20555 h sj A
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$j (Provided w/ Amendment 31)
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Enclosures:
- 1. License Condition for Leak Testing fl!
W Sealed Plutonium Sources, did 4/93 l 5 !
E 2. License Condition for Plutonium Alpha l N Sources, dtd 4/93 l 9 l l i
N 3. Guidelines for Decontamination of l I Facilities..., did 4/93 E!
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g SNM-696 Amendment 43 a MATERIALS LICENSE Docket rr Reference Number g p
g ,
SUPPLEMENTARY SHEET 70-734 N N
N y SAFETY CONDITIONS N N SAFETY CONDITIONS U N
N N S-1. Authorized use: For use in accordance with statements, representations, and conditions contained in N N Part ll " License Specifications" dated July 24,1981, and supplements dated March 16 and N N December 24,1982; February 4, November 14, and November 15,1983; April 10, April 12, June 28, N September 4, and September 7,1984; December 5,1985; May 23, September 25, and December 10, N N
1986; December 21,1987; March 4, March 9 (2), March 22, April 26, August 22, September 8, and N N
November 2,1988; May 25 and November 17,1989; June 27,1990; April 30 and September 27,1991; N N
March 5, March 18, June 24, and September 10,1992; January 20,1995; and in the "SVA N N
Decommissioning Plan" dated April 1,1990 (submitted by letter dated March 30,1990); August 22, N N
N 1990 (submitted by letter dated August 24,1990); June 15,1992; July 12 and August 23,1994; I N
N Group 6 Laboratories unrestricted use request dated August 12,1994; March 1,1995; Group 7 Laboratories unrestricted use request dated December 5,1995; Group 8B Laboratories unrestricted E N
N E use request dated August 23,1996; October 15,1996, and April 30, and Group 9 Laboratories unrestricted use request dated July 17,1997. N N
N N
N N S-2. Records of all safety-related reports and analyses shall be retained as follows:
N N
N N a. Copies of criticality and radiation safety analyses shall be retained for at least 2 years or for 6 I
N months after a project is terminated, whichever is longer.
N N
N N b. Copies of all other safety-related records (e.g., plant alterations and additions, abnormal occurrences associated with radioactivity releases, audits and inspections, instrument calibrations, N N
ALARA findings, training and retraining, personnel exposures, routine radiation and environmental N N
I N surveys) shall be retained for at least 2 years or longer if required by regulations.
N N
N N S-3. Notwithstanding the statements in Section 5.4.2 in the License Specification Volume (Part II), if double U
N batching is not credible, the maximum safe batch size shall be no more than 75 percent of the U
)
N minimum critical mass independent of the degree of water moderation and reflection. However, when i N
N the Th/U atomic ratio is 2 3.6 and the H/U s 20, the maximum safe batch size may be increased to 790 !
I g contained U-235 independent of whether double batching is credible.
N N
N U
N S-4. The Director QACD, upon recommendation of the appropriate manager within QACD, shall have N authority to require immediate termination of activities and/or corrective action in any situation which, in N N
N their judgment, could lead to the annecessary exposure of personnel to ionizing radiation, release of N
N radioactive material, loss or damage of property, or non-compliance with the license or a regulation.
N N
N N S-5. The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA Committee, shall N meet at least annually to review (1) reports of audits and inspections performed since the last ALARA N N review and (2) employee exposures and effluent release data to determine (a) if there are any upward U N
N trends developing in personnel exposures for identifiable categones of workers, types of operations, or N
N effluent releases, (b) if exposures and releases might be lowered in accordance with the ALARA N ce6 cept, and (c) if equipment for effluent and exposure control is being property used, maintained, and inspected. y The CRSC evaluation, recommendations, and corrective actions shall be documented and the report shall be sent to the appropriate operations managers and the Vice President, Finance and g g '
g Administration. y N N '
N N N N N .
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NQc FORM 374A U.S. NUCLEAR REoULATORY coMMISSloN PAGE 4 OF 7 PAGES g
License Number g g SNM-696 Amendment 43 g 1 MATERIALS LICENSE oocket or nererence Nurnber (
3
. SUPPLEMENTARY SHEET 70-734 g h
a y SAFETY CONDITIONS ' 'd 1
4 1
1 3 S-6. Radiological Work Permits (RWPS) shall be issued for all unplanned or non-routine work with licensed d 1 material not covered by a WA The RWP shall be signed by Health Physics management or a senior 5 1 staff member before related work can commence. A senior staff member shall be a Health Physics d Technician having a minimum of 5 years' exponence in radiation safety An evalustson of the safety 4 1
effectiveness of the permit shall be made upon completion of the work. 4 1
0 1
1 S-7. Radiation safety training, appropnate to the employee's needs, shall be gu v all new employees. 4 U
I d S-8. Radiation safety training and indoctrination shall be conducted by the Health Physics Manager or by a a 1 1 similarly qualified individual. The Health Physics Manager may delegate training in that portion of the a a course to an individual who is uniquely qualified to present it. 4 1 4 Continuous air sampling shall be conducte d in any area where licensed material can become airbome. U 1 S-9.
4 1
1 S-10. The location of air samplers shall be checked snnually and whenever any process or equipment 4 a changes are made to verify the representativeness of work area air sampling. In addition, the location d 1 of air samplers shall be checked at the commencement of operations in any area that has been d 1 shutdown for more 113..I 6 months to verify the representativeness of air sampling. 4 1 W 1 S-11. The laboratories in which plutonium in a dispersible form may be used shall have exhaust ventilation i systems separate from other building exhausts and shall provide dual HEPA filtering of the effluent air. 4 1
1 4 S-12. Sealed Plutonium sources shall be subject to the leak testing and actions specified in the attached i 1
1 " License Condition for Leak Testing Sealed Plutonium Sources," dated April 1993. 5 1 0 1 Plutonium alpha sources shall be subject to the actions specified in the attached " License Condition for 5 1 Plutonium Alpha Sources," dated April 1993. 5 1 4 1 S-13. Tne licensee shall prepare and submit to the Chief, Licensing Branch, Division of Fuel Cycle Safety and 5 i
1 Safeguards, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC 20555, a report whenever i
1 there is any new residential development within 1 mile around the site tnat constitutes a significant 1 change in parameters that may be affected by the release of radioactive materials into the environment, d 1 6 1 .S-14 Deleted by Amendment 14 dated August 3,1990 (originally numbered S-23 in 1990 - 1992 and 5 1 renumbered to S-14 in Amendment 23 dated October 7,1993). The information in License Condition d 1 S-23 was incorporated into License Condition S-9 by adding the date of May 25,1989; License i U
Condition S-9 later became S-1.
1l 1 4 1 S-15. At the end of plant life, the licensee shall decontaminate the site and facilities, authorized as a place of i 1 use for special nuclear material, in accordance with the general decommissioning plan submitted by 5 3 N your letter dated July 25,1986, and its supplement dated October 15,1986, so that these facilities and 1 I grounds can be released for unrestricted use. The corporate commitment that funds will be made I available for decommissioning the facility, provided by letter dated September 10,1986, is hereby I
I mcorporated as a condition of the license.
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g .
. SUPPLEMENTARY SHEET 70-734 g SAFETY CONDITIONS h E
N E
N N S-i r,. Release of equipment, facilities, or packages to the unrestricted area or to uncontrolled areas onsite E ,
N shall be in accordance with the attached " Guidelines for Decontamination of Facilities and Equipment E I Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special I!
N!
N Nuclear Material," dated April 1993. E, E
N N S-17. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and E released for general use. E N
N N
N S-18. Notwithstanding the statement in Section 4.2.1.4, Part il of the license, the trip levels will be readjusted E N after each monthly test of the criticality alarm system if the alarm point fails to activate within E approximately 5 seconds, more than once out of four trials. I!
N E
N S-19. Notwithstanding the statements in Section 4.2.1.4, Part ll of the license, no material handling shall be E N
allowed in any area in which the required criticality alann system is inoperative. E N
I!
ll!
S-20. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and Ei N
N released for general use. !!l El B
S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to the licensee I!
N N on October 3,1988. E!
I!
N N S-22. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and ;E El N released for general use.
E N
S-23. The licensee shall maintain and execute the response measures described in the Emergency Plan E N
N dated October 10,1997, supplemented by letter dated November 6,1997, or as further revised by the jl!
N licensee consistent with the provisions of 10 CFR 70.32(i). jE I!
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- Lkense Number fg g SNM-696 Amendment 43 lE, pocket or nererence Number p MATERIALS LICENSE Ei g . ,
SUPPLEMENTARY SHEET 70-734 gE i N
E I SAFEGUARDS CONDITIONS Ei 1 g
E 6
E j N
B SAFEGUARDS CONDITIONS lE i E
n l N
lE N SECTiON 1.0 - FACILITY ORGANIZATION lE {
y! E W Currently there are no license conditions in this section. The necessary information has been incorporated into E p cn approved plan. E E
N g SECTION 2.0 - FACILITY OPERATION E E
N Deleted by Amendment 37, September 1996. Not applicable under a possession only license. E N SG-2.1 g E Deleted by Amendment 37, September 1996. Not applicable under a possession only license. E B SG 2.2 N lE N SG-2,3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license, jE s lE d SG-2.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. !R E
R SECTION 3.0 - MEASUREMENTS E
9 SG-3.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
N
{EEl i N
W SG-3.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. E E
)
1 W
N SG-3.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. !R I 9
E W SECTION 4.0 - MEASUREMENT CONTROL E
9 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. E B SG-4.1 E
E B SG-4.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. {E E I! i )
Deleted by Amendment 37, September 1996. Not applicable under a possession only license. R' B SG-4.3 E j!i H SG-4.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. jR j
E H
N SG.4.5 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. ji h
B; SG-4.6 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. lEl' p- 'E !
E 5 SG-4.7 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
E, SG-4.8 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
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License Nurnber g
g SNM-696 Amendment 43 In M ATERI ALS LICENSE thlet or Reference Number g p I g
SUPPLEMENTARY SHEET 70-734
!g E
N g g SAFEGUARDS CONDITIONS '
E N
E N
N SECTION 5.0 - INVENTORY N lEE N SG-5.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. lE E
N N SG-5.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. E E
N N SG-5.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. E E
N E
N SECTION 6.0 - RECORDS AND REPORTS E
N Deleted by Amendment 37, September 1996. Not applicable under a possession only license. E N SG-6.1 E
N E
N SECTION 7.0 - INTERNAL CONTROL E
N R SG-7.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. lE j
'E j N
E N SECTION 8.0 - MANAGEMENT E
N E
N SG-8.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
N N
E N SECTION 9.0 -- PHYSICAL PROTECTION REQUIREMENTS FOR FORMULA QUANTITIES OF STRATEG E N SEECIAL NUCLEAR MATERIAL l E !
N B SG-9.1 The licensee shall follow the measures described in the physical protection plan entitled, " Fixed E )
E {
N Site and Transportation Plan for the Protection of Special Nuclear Material of Moderate and Low E
N Strategic Significance," dated May 1989, submitted by letter dated May 8,1989; and as it may be ]
E N further revised in accordance with the provisions of 10 CFR 70.32(e).
N N
E N SECTION -10.0 - TEMPORARY OR ONE TIME CONDITIONS N, 8 N SG-10.1 Deleted by Amendment 31, dated July 1995. jn !
jE N
B SG-10.2 Deleted by Amendment 31, dated July 1995. jn Nj E E
SG-10.3 Deleted by Amendment 31, dated July 1995.
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